22934 Federal Register / Vol. 76, No. 79 / Monday, April 25, 2011 / Notices 

site and its dose-mitigating engineered 

safety features remain acceptable with 

respect to the radiological consequences 

of postulated DBAs, since the calculated 

doses to members of the public meet the 

exposure guideline values specified in 

10 CFR 50.67 and General Design 

Criteria 19 in Appendix A of 10 CFR 

Part 50. If the NRC should approve LAR 

241, then the proposed EPU will not 

have a significant human health impact 

with respect to radiological 

consequences of DBAs. 

Radiological Impacts Summary 

As discussed above, the proposed 

EPU would not result in any significant 

radiological impacts. Table 2 

summarizes the radiological 

environmental impacts of the proposed 

EPU at the PBNP. 

TABLE 2—SUMMARY OF RADIOLOGICAL ENVIRONMENTAL IMPACTS

Radioactive Gaseous Effluents .......................... Amount of additional radioactive gaseous effluents generated would be handled by the existing 

system. 

Radioactive Liquid Effluents ............................... Amount of additional radioactive liquid effluents generated would be handled by the existing 

system. 

Occupational Radiation Doses ........................... Occupational doses would continue to be maintained within NRC limits. 

Offsite Radiation Doses ...................................... Radiation doses to members of the public would remain below NRC and EPA radiation protection standards. 

Radioactive Solid Waste ..................................... Amount of additional radioactive solid waste generated would be handled by the existing system. 

Spent Nuclear Fuel ............................................. Amount of additional spent nuclear fuel would be handled by the existing system. 

Postulated Design- Basis Accident Doses ......... Calculated doses for postulated design-basis accidents would remain within NRC limits. 

Alternatives to the Proposed Action 

As an alternative to the proposed 

action, the NRC staff considered denial 

of the proposed EPU (i.e., the ‘‘noaction’’ alternative). Denial of the 

application would result in no change 

in the current environmental impacts. 

However, if the EPU were not approved 

for the PBNP, other agencies and 

electric power organizations may be 

required to pursue other means, such as 

fossil fuel or alternative fuel power 

generation, to provide electric 

generation capacity to offset future 

demand. Construction and operation of 

such a fossil-fueled or alternative-fueled 

plant may create impacts in air quality, 

land use, and waste management 

significantly greater than those 

identified for the proposed EPU at the 

PBNP. Furthermore, the proposed EPU 

does not involve environmental impacts 

that are significantly different from 

those originally identified in the PBNP 

Unit 1 or Unit 2 FESs, and the SEIS–23. 

Alternative Use of Resources 

The action does not involve the use of 

any resources than those previously 

considered in the FES. 

Agencies and Persons Consulted 

In accordance with its stated policy, 

on April 6, 2011, the NRC staff 

consulted with the State of Wisconsin 

official regarding the environmental 

impact of the proposed action. The State 

official had no comments. Comments 

were received from the Wisconsin PSC 

and incorporated into the EA. The 

Wisconsin PSC has no objections to the 

projects as proposed. 

Finding of No Significant Impact 

On the basis of the details provided in 

the EA, the NRC concludes that the 

proposed action of implementing the 

PBNP EPU will not have a significant 

effect on the quality of the human 

environment. Accordingly, the NRC has 

determined not to prepare an 

environmental impact statement for the 

proposed action. 

For further details with respect to the 

proposed action, see the licensee’s 

application dated April 7, 2009, and 

supplements dated May 13, 2010, and 

July 15, 2010 (on environmental issues). 

Documents may be examined, and/or 

copied for a fee, at the NRC’s Public 

Document Room (PDR), located at One 

White Flint North, 11555 Rockville Pike 

(first floor), Rockville, Maryland 20852. 

Publicly available records are available 

online in the NRC Library at http:// 

www.nrc.gov/reading-rm/adams.html. 

From this page, the public can gain 

entry into ADAMS, which provides text 

and image files of the NRC’s public 

documents. Persons who do not have 

access to ADAMS or who encounter 

problems in accessing the documents 

located in ADAMS should contact the 

NRC PDR Reference staff at 1–800–397– 

4209, or 301–415–4737, or send an email to pdr.resource@nrc.gov. 

Dated at Rockville, Maryland, this 13th day 

of April 2011. 

For the Nuclear Regulatory Commission. 

Terry A. Beltz, 

Senior Project Manager, Plant Licensing 

Branch III–1, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2011–9835 Filed 4–22–11; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards (ACRS), Meeting of the 

ACRS Subcommittee on Reliability and 

Probabilistic Risk Assessment; Notice 

of Meeting 

The ACRS Subcommittee on 

Reliability and Probabilistic Risk 

Assessment (PRA) will hold a meeting 

on May 11, 2011, Room T–2B3, 11545 

Rockville Pike, Rockville, Maryland. 

The entire meeting will be open to 

public attendance. 

The agenda for the subject meeting 

shall be as follows: 

Monday, May 11, 2011—1 p.m. until 5 

p.m. 

The Subcommittee will hear a briefing 

on the plan and schedule for developing 

a level 3 PRA. The Subcommittee will 

hear presentations by and hold 

discussions with the NRC staff and 

other interested persons regarding this 

matter. The Subcommittee will gather 

information, analyze relevant issues and 

facts, and formulate proposed positions 

and actions, as appropriate, for 

deliberation by the Full Committee. 

Members of the public desiring to 

provide oral statements and/or written 

comments should notify the Designated 

Federal Official (DFO), John Lai 

(Telephone 301–415–5197 or E-mail: 

John.Lai@nrc.gov) five days prior to the 

meeting, if possible, so that appropriate 

arrangements can be made. Thirty-five 

hard copies of each presentation or 

handout should be provided to the DFO 

thirty minutes before the meeting. In 

addition, one electronic copy of each 

presentation should be emailed to the 

DFO one day before the meeting. If an 

electronic copy cannot be provided 


jdjones on DSKHWCL6B1PROD with NOTICES
Federal Register / Vol. 76, No. 79 / Monday, April 25, 2011 / Notices 22935 

within this timeframe, presenters 

should provide the DFO with a CD 

containing each presentation at least 

thirty minutes before the meeting. 

Electronic recordings will be permitted 

only during those portions of the 

meeting that are open to the public. 

Detailed procedures for the conduct of 

and participation in ACRS meetings 

were published in the Federal Register 

on October 21, 2010 (75 FR 65038– 

65039). 

Detailed meeting agendas and meeting 

transcripts are available on the NRC 

Web site at http://www.nrc.gov/readingrm/doc-collections/acrs. Information 

regarding topics to be discussed, 

changes to the agenda, whether the 

meeting has been canceled or 

rescheduled, and the time allotted to 

present oral statements can be obtained 

from the Web site cited above or by 

contacting the identified DFO. 

Moreover, in view of the possibility that 

the schedule for ACRS meetings may be 

adjusted by the Chairman as necessary 

to facilitate the conduct of the meeting, 

persons planning to attend should check 

with these references if such 

rescheduling would result in a major 

inconvenience. 

If attending this meeting, please 

contact Ms. Jessie Delgado (Telephone 

301–415–7360) to be escorted to the 

meeting room. 

Dated: April 19, 2011. 

Yoira Diaz-Sanabria, 

Acting Chief, Reactor Safety Branch B, 

Advisory Committee on Reactor Safeguards. 

[FR Doc. 2011–9918 Filed 4–22–11; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards (ACRS); Meeting of the 

ACRS Subcommittee on U.S. 

Evolutionary Power Reactor; Notice of 

Meeting 

The ACRS Subcommittee on U.S. 

Evolutionary Power Reactor (U.S. EPR) 

will hold a meeting on May 11, 2011, 

Room T–2B1, 11545 Rockville Pike, 

Rockville, Maryland. 

The entire meeting will be open to 

public attendance. 

The agenda for the subject meeting 

shall be as follows: 

Wednesday, May 11, 2011—8:30 a.m. 

Until 12 p.m. 

The Subcommittee will review 

Chapter 18 of the Safety Evaluation 

Report (SER) with open items associated 

with the review of the U.S. EPR Design 

Control Document (DCD). The 

Subcommittee will hear presentations 

by and hold discussions with AREVA, 

the NRC staff, and other interested 

persons regarding this matter. The 

Subcommittee will gather information, 

analyze relevant issues and facts, and 

formulate proposed positions and 

actions, as appropriate, for deliberation 

by the Full Committee. 

Members of the public desiring to 

provide oral statements and/or written 

comments should notify the Designated 

Federal Official (DFO), Derek Widmayer 

(Telephone 301–415–7366 or E-mail: 

Derek.Widmayer@nrc.gov five days 

prior to the meeting, if possible, so that 

appropriate arrangements can be made. 

Thirty-five hard copies of each 

presentation or handout should be 

provided to the DFO thirty minutes 

before the meeting. In addition, one 

electronic copy of each presentation 

should be emailed to the DFO one day 

before the meeting. If an electronic copy 

cannot be provided within this 

timeframe, presenters should provide 

the DFO with a CD containing each 

presentation at least thirty minutes 

before the meeting. Electronic 

recordings will be permitted only 

during those portions of the meeting 

that are open to the public. Detailed 

procedures for the conduct of and 

participation in ACRS meetings were 

published in the Federal Register on 

October 21, 2010, (75 FR 65038–65039). 

Detailed meeting agendas and meeting 

transcripts are available on the NRC 

Web site at http://www.nrc.gov/readingrm/doc-collections/acrs. Information 

regarding topics to be discussed, 

changes to the agenda, whether the 

meeting has been canceled or 

rescheduled, and the time allotted to 

present oral statements can be obtained 

from the Web site cited above or by 

contacting the identified DFO. 

Moreover, in view of the possibility that 

the schedule for ACRS meetings may be 

adjusted by the Chairman as necessary 

to facilitate the conduct of the meeting, 

persons planning to attend should check 

with these references if such 

rescheduling would result in a major 

inconvenience. 

Dated: April 19, 2011. 

Yoira Diaz-Sanabria, 

Acting Chief, Reactor Safety Branch B, 

Advisory Committee on Reactor Safeguards. 

[FR Doc. 2011–9920 Filed 4–22–11; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 72–8; NRC–2011–0085] 

Calvert Cliffs Nuclear Power Plant, LLC 

Independent Spent Fuel Storage 

Installation; Notice of Docketing, 

Notice of Proposed Action, and Notice 

of Opportunity for a Hearing for 

Renewal of Special Nuclear Materials 

License No.–2505 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of license renewal, and 

opportunity to request a hearing. 

DATES: A request for hearing and/or 

petition for leave to intervene must be 

filed by June 24, 2011. 

FOR FURTHER INFORMATION CONTACT: John 

M. Goshen, Project Manager, Licensing 

Branch, Division of Spent Fuel Storage 

and Transportation, Office of Nuclear 

Material Safety and Safeguards, U.S. 

Nuclear Regulatory Commission, 

Washington, D.C. 20555–0001. 

Telephone: 301–492–3325; fax number: 

301–492–3348; e-mail: 

john.goshen@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The U.S. Nuclear Regulatory 

Commission (NRC or Commission) is 

considering an application dated 

September 17, 2010, as supplemented 

February 10, and March 9, 2011, Calvert 

Cliffs Nuclear Power Plant (CCNPP), 

LLC, for the renewal of its Special 

Nuclear Material (SNM) License No.– 

2505, under the provisions of 10 CFR 

Part 72, for the receipt, possession, 

storage and transfer of spent fuel, 

reactor-related Greater than Class C 

(GTCC) waste and other radioactive 

materials associated with spent fuel 

storage at the CCNPP site-specific 

Independent Spent Fuel Storage 

Installation (ISFSI), located near Lusby, 

Maryland. If granted, the renewed 

license will authorize the applicant to 

continue to store spent fuel in a dry cask 

storage system at the applicant’s CCNPP 

ISFSI. Pursuant to the provisions of 10 

CFR 72.42, the renewal term of the 

license for the ISFSI would be twenty 

(20) years; however, the applicant has 

submitted an exemption request with 

the license renewal application, which, 

if granted, would allow the license to be 

renewed for 40 years. On February 16, 

2011, (76 FR 8872) the revised 10 CFR 

72.230(b) rule was published changing 

the renewal term to a period not to 

exceed 40 years to be effective May 17, 

2011. The exemption request is no 

longer required. The renewal 


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